ML20053D223
| ML20053D223 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/06/1982 |
| From: | Mardis D FLORIDA POWER CORP. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 3F-0482-20, 3F-482-20, TAC-48126, TAC-48844, NUDOCS 8206040204 | |
| Download: ML20053D223 (10) | |
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.P.o...w...e..r April 6,1982 t/3F-0482-20 File: 3-0-3-e Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Operation at 2300 MWt with Pump Power Monitors Bypassed
Dear Mr. Denton:
Florida Power Corporation hereby requests authorization to operate Crystal River Unit 3 at power levels up to 2300 MWt (90.4% Full Power) with the Reactor Coolant Pump Power Monitors bypassed. Enclosed as part of this request is supporting documentation which i
shows that DNBR criteria will not be violated (at this power level) for the worst case Reactor Coolant Pump coastdown event. Scaling of the Power Range Nuclear Instruments to read 2300 MWt equal to 100% Full Power is required to validate the analyses supporting this request.
Continued operation at 75% Full Power versus 90% Full Power causes a significant economic hardship for Florida Power and offers no apparent benefits. We, therefore, request an expedited review of this request.
Very truly yours,
&& 0kA*-
David G. Mardis Acting Manager Nuclear Licensing EWF:mm cc:
Mr. J. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 g
Atlanta, GA 30303 00\\
8206040204 820406 s%
PDR ADOCK 05000302 P
PDR General Office 3201 Thirty fourth Street South e P O. Box 14042. St Petersburg. F~.onda 33733 e 813-866-5151 m....-
9 J.
A*. Castanes, Product Management J
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Castomer or m.
K. D. Tuley, Safety Analysis (Ext. 2692) 2,.c Oate Reauirements For FPC Cycle a Oceration '.lithout ne oumo Sra us Trio i
Maren 8. 1982 This memo specifies the RPS requirements for FPC Crystal River-3 Cycle 4 operation without the pump status trip.
Recent licensing activities regarding the pump status trip have impeded FPC full power operation.
Operation without taking credit for the pump status trip could provide some relief, permitting continued operation at a lower power level.
This memo summarizes the requirements necessary for this reduced power operation, taking no credit. for the pump status tri p.
The memo will address a summary of requirements, the revised RC flow protection philosophy, the limiting transient analysis results, and a discussion of the requirem,ents.
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Summary of Recuirements (1)
The pump status trip will not be assumed for any transient or steady-state protection.
(2)
All RC flow coastdown protection will be provided by the power / imbalance / flow tri p.
(3)
The Reactor Operator will be required to prevent 2,1 or 0 RC pump operation, as per FPC Tech. Spec. Section 3.4.1.
(a)
Rcted thermal power will be limited to 2300 MWth.
The neutron flux ins #rumenta' '
tion in the RPS (all channels, all trips) will be calibrated such that 100% FP.
neutron power equals 2300 MWth heat balance power.
(5)
The flux / flow ratio of the power /inbalance/ flow trip will be maintained at or below 1.07, as given in Figure 2.2-1 of FPC Tech. Specs. Amend. 46.
The power /. imbalance setpoints of this trip will be maintained at the values-specified in the Amend. 46 Figure 2.2-1.
Revised RC Flow Protection Philosoohy The original Cycle 4 RC flow protection philosophy was presented in Reference 2,
.and addressed the protection provided by the two RPS trips power / imbalance / flow and pump status.
The reference noted both transient and steady-state protection, with this original transient protection sunnarized in Table 1.
{
The revised Cycle 4 RC flow protection philosophy relies only on the power / imbalance / flow trip for all RC flow-related protection, both steady-state and transient.
The only change from the original Cycle 4 philosophy, is that for l
transient protection, the flux / flow ratio will provide protection for all RC pump coastdown accidents.
As the 2/2 - 0/0 pump coastdown accident is limiting (i.e., fastest flow reduction of all coastdown events, see Ref. I for confirmation),
3
this accident will be used to deterime limitations on the flux / flow setpoint or the transient initial scwer level.
The revised Cycle a RC flow protection philosopny is summarized in Table 2.
Also, as discussed in Reference 2, only the power / imbalance / flow trip provides steady-state protection, so that the lack of a pump status trip does not impact steady-state protection.
It should be noted, however, that the operator will be required to prevent 2,1 or 0 pump operation, as required in FPC Tech. Spec. Section 3.4.1.
Limiting Transient Analysis Results As noted in the " Philosophy" section of this memo, the 2/2 - 0/0 pump coastdown accident is limiting when flux / flow trip protection is required for all coastdown events (i.e., when the pump status trip is not used).
An analysis of a Cycle 4 4 pump coastdown (4PCD) event relying only on flux / flow trip protection, was generated in Reference 1, and these results will now be reviewed.
The Reference 1 analysis assumed the standard 4PCD event with two exceptions:
(1) the value of Sm (the analysis flux / flow ratio - see Ref. 3) remained at a value of 1.13%FP/% flow (giving a Tech. Spec. flux / flow ratio of 1.07%FP/% flow--
see Reference 4), and (2) the initial power level was varied, so that minimum DNBR (MDNBR) could be plotted against initial power level, still assuming Sm = 1.13.
t The reference recommends an initial power level of 2300 MWth, yielding a MDNBR 1 1.43 for the 4PCD with Sm = 1.13 (see Figure 1).
The limit on DNBR for FPC Cycle 4 is 1.35 (see Reference 1), so the 2300 MWth initial power level with Sm = 1.13 yields acceptable results.
It should be noted that 2300 MW is the assumed rated thermal th power; analysis of transients using the flux / flow trip normally assume neutron flux and ICS errors in the analysis initial power level.
If the plant initial power level is 100% FP, the transient analysis would assumed 108%FP (see References 1 and 3), yielding, for the FPC JPCD,108 x 2300 = 2484 MWth analysis initial power level.
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TABLE 1 ORIGINAL CYCLE 4 MATRIX OF RC FLC'J RECUCTICN ACC: DENT PROTECTION (ASSUMING PUMP STATUS TR!? CPERABLE; FOR CRYSTAL RI'/ER-3 ACCIDENT _
RPS TRIP PROTECTION RC Pump Coastdown 2/2 - 2/1 flux / flow ratio of power / imbalance / flow all other coastdowns pump status All Locked Rotor Accidents flux / flow ratio of power / imbalance / flow 2/2 denotes 4 pump status with 2 pumps operating in both steam generator loops.
177 FA plants currently do not analyze the sheared shaft event, but tactically assume this event is bounded by the locked rotor event.
If shear shaft protection were specified, it would be provided by the flux / flow ratio.
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TABLE 2 REVISED CYCLE a MATRIX OF RC FLOW REDUCTION ACCIDENT PROTECTION (ASSUMING NO PUMP STATUS TRIP)
FOR CRYSTAL RIVER-3 ACCIDENT RPS TRIP PROTECTION RC Pump Coastdown Accident 2/2 + 0/0
- flux / flow ratio of power / imbalance / flow all other coastdowns flux / flow ratio of power / imbalance / flow All Locked Totor Accidents flux / flow ratio of power /imtalance/ flow 2/2 denotes 4 pump status with 2 pumps operating in both steam generator loops.
177 FA plants currently do not analyze the sheared shaft event, but tactically assume this event is bounded by the locked rotor event.
If shear shaft protection were specified, it would be provided by the flux / flow ratio.
- This protection may require flux / flow setpoint reduction and/or power derating to provide acceptable DNBR protection.
7
To su:mnarize these results the transient analysis assumed a 2300 MWth rated e
power with the ccmouter code analysis using 2234 MWth' Sm
- I 13 Sew = 1.07, and the resulting DilBR was 1.43, above the 1.35 limit.
Discussion of Recuirements Requirement 1 - Purpose of file Requirement 2 - As noted in " Philosophy" section, the flux / flow ratio will supplant the transient protection previouslt provided by the pump status trip.
Requirement 3 - The pump status trip prohibits operation in 2,1 or 0 RC pump status.
As the pump status t. ip will no longer be assumed for any protection, the reactor operator must be cognizant for ensuring
. that the plant does not operate in 2,1 or 0 pump status, and that
- the operator will manually ensure that Tech. Spec. Section 3.4.1 is not violated.
Requirement 4 - The execution of an RPS trip is an exercize in evaluating the relation-ships of the generated voltage signals.
The limiting transient analysis made assumptions concerning the RPS calibration and the execution of the flux / flow trip based upon perceived flux and flow values.
Failure to calibrate flux to 100% FP (or s 8.0 volts in the 0-10 volt range) at 2300 MW heat balance power will alter th the calculated event consequences of the 4PCD.
b
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' Rbq'uire. ment 5 - The flux /ficw ratio setpoint is a similar analysis assumption, necessary to ensure acceptable event consequences.
With a 1.07 flux / flow ratio, a timely reactor trip will be actuated, generating the acceptable JPCD consequences discussed in the " Limiting Transient Analysis" section.
Higher values of the flux / flow ratio setpoint could result in more severe 4PCD event consequences, as discussed in Requirement 4.
liaintaining the power / imbalance setpoints ensures conservative steady-state DNBR and kW/ft protection, as noted in Reference 4.
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REFEREtlCES:
I 1.
11.0. yalz to K.D. Tuley, " Operation Without Pump itonitors," 86-1131326-00, 660-083D, 3/25/82.
2.
K.D. Tuley, "FPC RPS Recuirements for RC Flow-Related Trips," 51-1128452-02, 585-7087, 1/13/82.
3.
X.D. Tuley, "FPC 0/W Setpoint Error Adjustment," 51-1132039-00, 660-083D, 3/30/02.
4.
R.H. Ellison, "RPS Setpoint Verification for 2300 ftWt' for CR-III Cy 4,"
32-1132041-00, 660-082D, 3/30/82.
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